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1
Content available remote

Comparison of Lead and WC-Co Materials against Gamma Irradiation

100%
Buyuk B., Tugrul A.
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vol. 125
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issue 2
423-425
EN
According to RoHS (Restriction of Hazardous Substances) directive of European Union it is restricted using lead in many equipment and applications. It is possible to enlarge the restriction of lead usage in some other applications which is including some of nuclear applications in the future. Therefore new materials or systems need to be developed instead of lead as radiation shielding materials and/or collimators. In this study pure tungsten, tungsten carbide-cobalt (WC-Co) materials were investigated against gamma radiation. For gamma radiation Cs-137 and Co-60 gamma radioisotope sources were used. The linear and mass attenuations were calculated. The experimental results were compared with XCOM computer code. Usage possibilities of WC-Co instead of lead in nuclear applications as gamma shielding material were discussed. It has been investigated that the linear gamma attenuation coefficients of lead and WC-Co are very close to each other. Therefore it could be said that WC-Co materials is an alternative promising material which could be used instead of lead as gamma shielding material and/or collimator.
2
Content available remote

The Chronic Dose Assessment of Three Critical Organs for Liver Scintigraphy with Using Cr-51

100%
Marancı Ö., Tugrul A.
Acta Physica Polonica A
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2017
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vol. 132
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issue 3
476-478
EN
In this study, a dosimetric study was observed by using Cr-51 gamma radioisotope on liver scintigraphy. In this context, the source organ is determined as liver and it is aimed the evaluation of measuring doses from source organ to selected three critical organs (thyroid, gonad, and brain). An antropomorphic torso phantom has been preferred in the experiments. The measurements of critical organs doses were examined for chronic effects. Moreover, the chronic effect of Cr-51 radioisotope on critical organs was determined as cumulative dose. Thermoluminescent dosimeters were used for chronic dose assessment. In the experiments, lithium fluoride (LiF) (TLD-100) detectors were used and they were provided from Turkish Atomic Energy Authority - Cekmece Nuclear Research and Training Center and calibrated in there. Within this study, the evaluation of the cumulative doses by using Cr-51 for three critical organs was observed with an original setup by using anthropomorphic torso phantom experimentally.
3
Content available remote

Gamma Attenuation Properties of Some Aluminum Alloys

81%
Yıldırım S., Tugrul A., Buyuk B., Demir E.
Acta Physica Polonica A
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2016
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vol. 129
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issue 4
813-815
EN
In the present work, several commonly used aluminum alloys were investigated for their protective properties against gamma radiation. The gamma transmission technique was used to study the gamma attenuation behavior of the alloys. Cs-137 (0.662 MeV) and Co-60 (1.25 MeV) gamma radioisotope sources, which have relatively medium and high gamma energy levels, were used as gamma sources. The linear and mass attenuation coefficients of the aluminum alloys were measured. The mass attenuation coefficients of the samples were compared with the theoretical values which were calculated using XCOM computer code. The difference between the experimental and theoretical values was below 5%. In addition half-value layer (HVL) values for the studied aluminum alloys were calculated using the linear attenuation coefficients. The attenuation coefficients of the different aluminum alloys were compared. The biggest HVL was observed for 1050 alloy, for both gamma isotope sources, which means the smallest gamma attenuation capability among the studied alloys. It is concluded that the alloys were applicable for the gamma radiation shielding applications.
4
Content available remote

Investigation of Behaviour of Titanium Diboride Reinforced Boron Carbide-Silicon Carbide Composites against Cs-137 Gamma Radioisotope Source by Using Gamma Transmission Technique

81%
Buyuk B., Tugrul A., Akarsu A., Addemir A.
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EN
Boron carbide is a material which has wide application areas in industry including nuclear technology. Titanium diboride reinforced boron carbide-silicon carbide composites were studied for searching of the behaviour against the gamma ray. It has been adopted that depending on their properties such improved materials can be used in nuclear technology. For the investigation of the gamma radiation behaviour of these materials, Cs-137 radioisotope was used as gamma source in the experiments which have a single gamma-peak at 0.662 MeV. Gamma transmission technique was used for the measurements. Different reinforcing ratios, titanium diboride reinforced boron carbide-silicon carbide composites were evaluated in relation to gamma transmission and the results of the experiments were interpreted and compared with each other. It could be understood that the increasing ratio of titanium diboride in boron carbide-silicon carbide composites causes higher hardness, strength and linear attenuation coefficient values but decrease the mass attenuation coefficient.
5
Content available remote

Investigation on the Effects of Boron Carbide Particle Size on Radiation Shielding Properties of Boron Carbide-Titanium Diboride Composites

81%
Buyuk B., Tugrul A., Aktop S., Addemir A.
Acta Physica Polonica A
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2013
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vol. 123
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issue 2
177-179
EN
Boron carbide is a material which has wide application areas in industry including nuclear technology. Titanium diboride-boron carbide composites which were produced from different boron carbide particle sizes were studied for searching of the behaviour against the gamma ray. Micron size and submicron size boron carbide were used to produce composite materials. The volume of boron carbide and titanium diboride in the composites are 85% and 15%, respectively. For the investigation of the gamma radiation behaviour of these materials, Cs-137 radioisotope was used as gamma source in the experiments which has a single gamma-peak at 0.662 MeV. Gamma transmission technique was used for the measurements. The effects of boron carbide particle size on radiation attenuation of titanium diboride-boron carbide composites were evaluated in relation with gamma transmission and the results of the experiments were interpreted and compared with each other. It could be understood that decrease of particle size of boron carbide in boron carbide-titanium diboride composites causes higher linear and mass attenuation coefficient values. So, submicron size boron carbide used composite materials are more convenient than micron size boron carbide used composite materials as radiation shielding materials for nuclear applications.
6
Content available remote

Assessment of Patient Dose by Positron Emission Tomography (PET) and Medical Internal Dose (MIRD) Methods

71%
Yilmaz G., Tugrul A., Demir M., Yasar D., Demir B.
Acta Physica Polonica A
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2016
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vol. 130
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issue 1
90-92
EN
Dynamic experiments cannot be observed easy on patients for determination of dosimetry in human PET studies dosimeter studies. In this study, it is aimed to estimate dose amount absorbed by some critical organs (e.g. bladder, lung, thyroid and ovary) by using a developed phantom. The phantom was improved as an original anthropomorphic whole body phantom which has been arranged with dynamic system. Therefore, organ absorbed doses by applying of fluorine-18-fluorodeoxyglucose in PET studies and was observed by using the phantom, while TLD dosimeters were used for determination of internal absorbed doses. In medical physics, the accuracy of absorbed dose resulting from radiopharmaceutical application was determined by the medical internal radiation dose method that depends theoretically on the cumulated activity of the source organs and their mass. The MIRD calculation was also used for the study and comparatively evaluated with the experimental results which were collected by using improved phantom.
7
Content available remote

Comparison of Radiation Properties of Tungsten and Additive Metal Coatings on 321 Stainless Steel Substrate

62%
Demir E., Karabas M., Sonmez S., Tugrul A., Ovecoglu M., Buyuk B.
Acta Physica Polonica A
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2017
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vol. 131
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issue 1
71-73
EN
In the present work, the gamma and neutron attenuation behaviors of tungsten, tungsten copper, and tungsten boron-carbide coatings on 321 stainless steel substrate were investigated against Cs-137 and Co-60 gamma radioisotopes and Pu-Be neutron source. The experimental results were compared and evaluated with pure 321 stainless steel to obtain gamma and neutron shielding properties of the coating materials. Tungsten, tungsten copper, and tungsten boron-carbide coatings on 321 stainless steel substrate were fabricated by atmospheric plasma spraying technique. Gamma and neutron transmission technique were used in this study to investigate the radiation behaviors of the coated materials. Linear attenuation coefficients of coated samples were carried out for Pu-Be neutron source. Transmittance values for each specimen were calculated at 0.662 MeV and 1.25 MeV gamma energies. The experimental results were evaluated for radiation shielding properties of the coated samples against gamma and neutron source with pure 321 stainless steel.
8
Content available remote

Processing, Mechanical and Nuclear Characterization of Boron Carbide Ceramics Consolidated by Spark Plasma Sintering

62%
Cengiz M., Ozer S., Buyuk B., Tugrul A., Yucel O., Goller G., Sahin F.
Acta Physica Polonica A
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2015
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vol. 128
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issue 2B
B-187-B-189
EN
Boron carbide (B₄C) ceramics were produced by spark plasma sintering technique with 5, 10, 15, and 20 vol.% aluminum (Al) in order to improve sintering behaviours of B₄C ceramics. B₄C ceramics were produced, having square cross-section and 50 × 50 × 5 mm³ dimensions. The sintering process was carried out at different temperatures by applying 40 MPa of pressure with 100°C/min under vacuum. The effects of various amounts of Al additive and sintering temperature on density, vickers hardness, fracture toughness and microstructure were examined. The hardness and fracture toughness of the samples were evaluated by the Vickers indentation technique. Microstructures of the samples were characterized by scanning electron microscopy technique. Fast neutron attenuation properties of the ceramics having highest density were also investigated.
9
Content available remote

Radiation Shielding Effect of Boron Carbide Aluminum Metal Matrix Composite

62%
Akkaş A., Tugrul A., Addemir O., Marşoğlu M., Ağacan B., Büyük B.
Acta Physica Polonica A
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2015
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vol. 127
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issue 4
947-949
EN
Boralyn (Al/B₄C) composite material is produced chiefly of boron carbide and aluminum. Boron Carbide is an important material for the nuclear industry due to high neutron absorption cross-section. This composite is used as shielding materials to absorb neutrons in the nuclear reactors and control road materials. In this study we investigated Al/B₄C composites against gamma radiation. For that purpose, 5 wt.%, 10 wt.%, 15 wt.% and 20 wt.% reinforcement content were investigated. Cs-137 gamma radioisotope source which has 662 keV gamma energy photons were used. For each material, linear and mass attenuation coefficients were calculated. Theoretical mass attenuation coefficients were calculated from XCOM computer code. The theoretical results were compared with experimental results. The results were showed that increasing the amount of Boron Carbide compound content of boralyn composite material decrease the linear and mass attenuation coefficient of materials
10
Content available remote

Shielding Effect of Boron Carbide Aluminium Metal Matrix Composite against Gamma and Neutron Radiation

62%
Akkas A., Tugrul A., Buyuk B., Addemir A., Marsoglu M., Agacan B.
Acta Physica Polonica A
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2015
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vol. 128
|
issue 2B
B-176-B-179
EN
In this study, boralyn (boron carbide-aluminum metal matrix composite material - Al/B₄C) composite materials were investigated on shielding effect against gamma and neutron radiations. The samples were prepared as 5 wt%, 10 wt%, 15 wt%, and 20 wt% reinforcement content and for each content of material has composed in five different average particle sized (3 μm, 53 μm, 113 μm, 200 μm, and 500 μm). Linear and mass attenuation coefficients were calculated experimentally for each composite material against Cs-137 gamma source. Theoretical mass attenuation coefficients of material were calculated by using XCOM computer code. Then the theoretical results were compared with experimental results. Then, macroscopic cross-section values were calculated experimentally for each composite material against Pu-Be neutron source. As the conclusion of the study, it could be understood that in spite of decrease of the attenuation coefficient against gamma radiation, the adding materials give rise to increase the shielding ability of material against neutron radiation.
11
Content available remote

Radiation Shielding Properties of Spark Plasma Sintered Boron Carbide-Aluminium Composites

62%
Buyuk B., Tugrul A., Cengiz M., Yucel O., Goller G., Sahin F.
Acta Physica Polonica A
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2015
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vol. 128
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issue 2B
B-132-B-134
EN
In this study gamma and neutron attenuation properties of boron carbide-aluminium (B₄C-Al) composites were investigated. B₄C-Al composites were produced by spark plasma sintering method. Aluminum percentages in the B₄C-Al composites were 0%, 10%, 15%, and 20% by volume. The composite materials were performed against gamma and neutron sources. Cs-137 and Co-60 gamma radioisotopes were used as gamma sources and Pu-Be neutron howitzer was used for neutron source. Theoretical mass attenuation coefficients were determined by using XCOM computer code and compared with the experimental results. It has been seen that the experimental results were close to the theoretical results. Total macroscopic cross-sections of the samples were determined for Pu-Be neutrons. It is concluded that increasing aluminum ratio in the B₄C-Al composites causes higher gamma attenuation behavior for Cs-137 and Co-60 gamma sources and the total macroscopic cross-sections of the B₄C-Al composites decrease by increasing Al concentration.
12
Content available remote

Investigation of Natural Radioactivity of Surface Soil Samples in the Vicinity of Edirne-Turkey

62%
Zaim N., Tugrul A., Atlas H., Buyuk B., Demir E., Baydogan N., Altınsoy N.
Acta Physica Polonica A
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2016
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vol. 130
|
issue 1
64-67
EN
The study was carried out to determine radioactivity concentrations in surface soil samples of the city of Edirne in connection with the potential radiological hazards due to Chernobyl event. The natural radionuclide ((226)Ra, (232)Th and (40)K) contents were determined for nine different locations in nine different towns of the Edirne city. Radiation levels were measured. Natural beta-ray activity was also determined for the same locations. The average estimated activity values were determined and compared with reported values for other cities in Turkey and also for many countries of the world. The studied areas do not pose radiological risks to the inhabitants due to harmful effects of the ionizing radiation from the natural radioactivity of the soil.
13
Content available remote

Assessment on Gamma Attenuation Behavior of W-VC-C and W-VC-TiC-C Composites for Co-60 Radioisotope

62%
Demir E., Tugrul A., Sonmez S., Ovecoglu L., Buyuk B., Yilmaz O.
Acta Physica Polonica A
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2017
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vol. 132
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issue 3
830-832
EN
In this study, tungsten-vanadium carbide-graphite (W-VC-C) and tungsten-vanadium carbide-titanium carbide-graphite composite (W-VC-TiC-C) materials were investigated against Co-60 gamma radioisotope. The composite materials which are used in advanced technological studies and high temperature applications in many various fields especially in the areas of fission and fusion armor materials were produced by mechanical alloying method as in two groups. One of them include 93% tungsten (W), 6% vanadium carbide (VC) and 1% graphite (C) also which has three different alloying times (6-12-24 h). Other group of the samples was composed of 91% tungsten, 6% vanadium carbide (VC), 2% titanium carbide (TiC) and 1% graphite (C) also which has three different alloying times (6-12-24 h) and sintered at 1750°C. Co-60 gamma radioisotope source and gamma transmission technique were used in the experiments to investigate the properties of the composite materials. The mass attenuation coefficients of the samples were determined by using experimental results and theoretical mass attenuation coefficients were calculated from XCOM computer code. It can be concluded that increasing the tungsten ratio causes higher mass attenuation coefficient and the composite materials have provided us benefits better than lead for radiation gamma shielding.
14
Content available remote

Investigation for Remediation of Selenium Aqueous Environment with Using Organic Pillared Bentonite by Radiotracer Technique

42%
Tugrul A., Haciyakupoglu S., Erenturk S., Karatepe N., Baytas F., Baydogan N., Altinsoy N., Buyuk B., Orucoglu E., Demir E., Camtakan Z., Okka M.
Acta Physica Polonica A
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2015
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vol. 127
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issue 4
1186-1188
EN
In this study remediation of selenium ions from aqueous solutions was investigated using organic pillared bentonite as an adsorbent. Organic pillared bentonite was produced from Resadiye (Tokat, Turkey) bentonite using hexadecylpyridinium chloride and aluminum polyoxy-cations. All the experiments were carried out by tracing with selenium radioisotope. For the production of the radioactive selenium radioisotope, selenium dioxide was irradiated in the central thimble of ITU TRIGA Mark II Training and Research Reactor at Energy Institute of Istanbul Technical University. Radioactivity measurements carried out by the gamma-ray spectroscopy system were used to determine of selenium isotope. The relative importance of test parameters like concentration of adsorbate, pH of the solution and contact time on adsorption performance of organic pillared bentonite for selenium ion was studied. Evaluation of experiments for different parameters showed possibility of remediation of selenium from aqueous media by using organic pillared bentonite.
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